ML19322A218
| ML19322A218 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/11/1979 |
| From: | Herbein J METROPOLITAN EDISON CO. |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| GQL-0069, GQL-69, NUDOCS 7901160199 | |
| Download: ML19322A218 (10) | |
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TELEPHONE 215 - 929-3601 POST OFFICE Box 542 RE ADING, PENNSYLV ANI A 19603 January 11, 1979 GQL 0069 Director of Nuclear Reactor Regulations Attn:
R. W. Reid, Chief Operating Reactors Branch No. 4 U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Sir:
Three Mile Island Nuclear Station, Unit 1 (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Technical Specification Change Request No. 87 (Additional Information)
As a result of the January h,1979 conference call with Chris Nelson, et.al. of your staff, and subsequent conversations with NRC's Mr. Clemenson and Mr. Nelson, the following additional information is submitted. This information supports lifting of the fuel pool gate on a one-time-only basis, per NRC direction.
Calculations were perfomed in accordance with Reg. Guide 1.25 to determine the exclusion boundaiy doses assuming release of all gaseous fission products from the irradiated fu,;i in either spent fuel pool. These calculations were per-formed using NRC's recommended X/Q valve of 8.2 x 10. Results of the cal-culations (Attachment 1) indicate that for 60 assemblies with less han 180 days cooldown, no assemblies with less than 28 days cooldown, and the remainder of either fuel pool with greater than 180 days cooldown, the dose at the ex-clusion boundary is 229 Rem thyroid and 3 Rem whole body gamma, well below the 10 CFR 100 limits of 300 Rem thyroid and 25 Rem whole body gamma. The proposed revised Technical Specifications (Attachment 2) require that either the lifting devices be redundant with each device capable of supporting three times the static plus dynamic load of the gate, or where not redundant, the lifting devices be capable of supporting greater than six times the static plus dynamic load of the gate. This specification, applicable for a one-time-only lifting of the gate, asrures that either a single failure vill not result in a drop for the case of redundant lifting devices, or sufficient margin exists such that a failure vill not occur for the case of a single lifting device.
Also attached (Attachment 3) is a description of the proposed lifting lug mod'fication.
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2-January 11, 1979
- R. W. Reid
- GQL 0069 Met-Ed requests that the revised proposed Technical Specifications ( Attachment 2) f replace the proposed Technical Specifications submitted on December 26, 1978 (GQL 2056).
Sincerely
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1 J. G. Herbein Vice President-Generation JGH:RJS:Jdp Attachments: 1)
Dose Calculations (3 pages) 2)
Revised Proposed Technical Specifications (3 pages) 3)
Proposed Lifting Lug Modification (2 pages)
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Attachm:nt 1 Pags 1 of 3
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DOSE AT EXCLUSION BOUNDARY FOR THE FOLLOUING CONDITIONS:
I NO. OF ASSEMDLIES FAILED-'60 NO. OF HOURS SINCE FUEL WAS IRRADIATED-672 EFFECTIVE IODINE DECONTAMINATIO,? FACTOR FOR POOL WATER-100
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EFFECTIVE IODINE DECONTAMINATION FACTOR FOR FILTERS-6.6667 PEAKING FACTOR OF 1.7 X/Q VALUE OF-8.2E-4
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- RELEASE TO ATMOSPHERE BASED ON THESE ASSUMPTIONS (IN CURIES)*****
ISOTOPE ACTIVITY
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KR-85M 1.4207E-40 KR-85 146912
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KR-87 O
KR-80 0
XE-131M 6710.1
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XE133M 36.305 XE-133 202934 XE-135M O
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XE-135 1.3431E-16 I-131 543.05 I-132 0
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I-133 2.5366E-6 I-134 0
I-135 7.8731E-27
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- CALCULATED DOSES *****
THYROID DOSE-228.69 REM
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WHOLE BODY DOSE GAMMA-1.5809 REM WHOLE BODY DOSE BETA-12.065 REM
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Page 2 of 3 I
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DOSE AT EXCLUSION DOUNDARY FOR THE FOLL0tJING CONDITIONS-NO. OF ASSEMBLIES FAILED-196
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NO. OF HOURS SINCE FilEL WAS IRRADIATED-4320 EFFECTIVE 10 DINE DECONTAMINATION FACTOR FOR P001 UATER-100 EFFECTIVE IODINE DECONTAMINATION FACTOR FOR FILTERS-6.6667
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PEAKING FACTOR OF i.7 X/O VALUE OF- 0.2E-(
- RELEASE TO ATMOSPHERE BASED ON THESE ASSUMPTIONS (IN CURIES)*****
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ISOTOPE ACTIVITY
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KR-85M O
KR-85 467184 KR-07 0
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KR-08 0
XE-131M 3.2736 XE133M 6.7268E-19
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.0013772 XE-135M O
XE-135 0
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.0037624 I-132 0
I-133 0
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I-134 0
I-135 0
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- CALCULATED DOSES *****
THYROID DOSE-3015844 REM WHOLE BODY DOSE GAMMA-.20219 REN
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WHOLE BODY DDSE BETA-20.53 REM i
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Atttchm;nt 1 Page 3 of 3
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DOSE AT EXCLUSION D0tlNDARY FOR Tile FOLLOWING CONDITIONS:
NO. OF'ASSENDLIES FAILED-436 NO. OF HOURS SINCE FUEL WAS IRRADIATED-4320 EFFECTIVE IODINE DECONTAMINATION FACTOR FOR POOL WATER-100
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EFFECTIVE IODINE DECONTAMINATION FACTOR FOR FILTERS-6.6667 PEAKING FACTOR OF_i.7 X/Q VALUE OF- 0.2E-4
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- RELEASE TO ATMOSPHERE BASED ON THESE ASSUMPTIONS (IN CURIES)*****
ISOTOPE ACTIVITY
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KR-85M O
KR-85 1039247 j.(
KR-87 0
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KR-80 0
XE-131M 7.2022
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XE133M 1.4964E-18 L
.0030636 XE-135M 0
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XE-135 0
.0083695 I-132 0
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I-133 0
I-134 0
I-135 0
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- CALCULATED DOSES *****
THYROID DOSE-.0035246 REM
.g WilOLE DODY DOSE GAMMA-.44977 REM knGLE BODY DOSE BETA-45.668 REM
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3.11 Haniling of Irradiated Fuel Anolicability Applies to the opera:ica of the fuel handling building crane when within the confines of Unit 1 and there is any spent fuel in storage in the Unit 1 fuel handling building.
Objective To define the lift conditions and al'ovable areas of travel when loads to be lifted and transported with the fuel handling building crane are in excess of 15 tons or between 3000 lbs. and 15 tons or consist of irradiated fuel elements.
Seecification 3 11.1 Spent fuel elenents having less than 120 days for decay of their irradiated fuel shall not be loaded into a spent fuel transfer cask in the shipping cask area.
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3.11.2 The key operated travel incerlock system for automatically limiting g
the travel area of the fuel handling building crane shall be imposed vhenever loads in excess of 15 tons are to be lifted and transported I
with the exception of fuel handling bridge maintenance.
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i 3.11.3 The lowest surface of all loads in excess of 15 tons shall be administratively limited to an elevation one foot or less above the t
concrete surface at the noninal 3h8 ft-0 in. elevation in the fuel l
handling building.
3.11.h Leads in excess of hook capacity shall not be lifted, except for t'
load testing.
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.3 11 5 Following modifications or repairs to any of the load bearing members, the crane shal' be subjected to a test lift of 125 percent of its rated lead.
3 11.6 Except as specified in 3.11.2 and 3.11.3 above, loads in excess of 3000 lbs. shall be administratively controlled so that they are handled at the lowest practicable elevation and so that the center of mass of the load is:
(1) maintained belov elevation 3h8 ft-0 in. or (2) maintained at such distance from the edge of a fuel storage pool containing irradiated fuel that should the load be released and tip over (such that the long dimension of the load was substantially horizontal) in any direction, the center of mass of the lead vould be at least six feet from the edge of any pool containing irradiated fuel.
3.11.7 A spent fuel shipping cask shall not be permitted in the Unit 1 Fuel Handling Building.
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Attachm:nt 2 Page 2 of 3 l
3.11.8*
Specification 3.11.6 does not apply to the gate between the spent fuel pools when transferring it between its functional location and its storage location provided:
There are no more than 60 irradiated fuel assemblies with less than a.
180 days cooling time in either fuel pool.
b.
There are no irradiated fuel assenblies with less than 30 days cooling time in either fuel pool.
The lifting uevices that are attached between the load block and the c.
gate are redundant, and each device is capable of supporting three times the static plus dynamic load of the gate, or where not redundant, each device is capable of supporting greater than six times the static plus dynamic load of the gate.
- Specification 311.8 is applicable on a one-time-only basis to permit removal of the fuel pool gate from its functional location. The gate shall be removed from its func-tional Jocation prior to the Cycle 5 refueling outage.
_3 aces T51s' ' specification vill 1N4t activity releases to unrestricted areas resulting fraca danage to spent fuel stored in the spent fuel storage pools in the postulated event p
of the dropping of a hearf load from the fuel handling building crane. Vnen a loaded spent fuel transfer cask is moved out of the deconte4 ation. pit area and along the
[7 centerline of the spent fuel pool's vest vall to the receiving / shipping area (Figure 9-18, Section 9), it has a poteny pwas performed assuning that the cask and its entire drop of k3 feet which is 13 feet greater than its desis;n basis drop. An analysis centents of ten fuel assenblies are sufficiently danaged as a result of dropping the cask, to allow the escape of all noble gases and iodine in the gap.
This release was assumed to be directly to the atmosphere and 'to occur instantaneously. The site is boundary doses resulting from this accident are 5.25 R whole body and 1.02 R to thyroid, and are within the limits specified in 10 CFR 100.
Specification 3.11.1 requires that spent fuel, having less than 120 days decay' post-irradiation, not be loaded in a spent fuel transfer cask in order to ensure that the
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doses resulting from a highly improbable spent fuel transfer cask drop would be within those calculated above.
Specification 3.11.2 requires the key operated interlock system, which automatically W 4ts the travel area of the fuel handling crane (refer to Figure 9-18A, Section 9) while it is lifting and transporting the spent fuel shipping cask, to be imposed whenevem loads in excess of 15 tons are to be lifted and transported while there is any spent fuel, in storage in the spent fuel storage pools in Unit 1.
This automatically ensures that these heavy loads travel in areas where, in the unlikely event of a load drop accident, there vould be no possibility of this event resulting in any da"Be to the spent fuel stored in the pools or doing any unacceptable structural M e,ge to the cpent fuel pool structure. As described in Section 9.7.1.1, the shipping cask area is designed to vith-stand the drop of the spent fuel shipping cask fron an elevation of 3h9 ft without unacceptable damaga to the spent fuel pool structure.
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Attachmint 2 Page 3 of 3 Specification 3.n.3 ensures that the icvest surface of any hea,rf load never gets higher than one foot above the concrete surface of i,he 3h3 ft-0 in. elevation in the fuel handling building (nceinni elevation 3h9 ft-0 in. ) thereby keeping any i= pact force from an unlikely load drop accident within acceptable li=its.
Specification 3.11.h c:gres that the proper capacity crane hock is used for lifting and transporting loads snus reducing the probability of a load drop accident.
Following nodification or repairs, specification 3.11.5 confir:s the load rating of the crane.
Specification 3.11.6 impcses administrative li=its en handling 1 cads veighing in excess of 3000 lbs. tc prevent damage to irradiated fuel.
Handling loads of less than 3000 lbs. without those restrictions is acceptable because the consequences of dropping loads in this weight range are ec= parable to those produced by the fuel bandling accident considered in the FSAR and found acceptable.
Specification 3.11,7 prohibits the presence of a spent 'nel cask in the Unit 1 Fuel Hano h g Suilding. This prohibition vill be retained until the :iRC has completed its reviev of spent fuel cask handling operations at T".I-1 and concluded that such operations can be performed safely.
Specification 3.11.8 permits the movement of the gate between the spent fuel pools.
The irradiated fuel inventory /cooldown requirements are to prevent exceeding 10 CFR -
100 dose limits should th; cate be dropped, causing fission product releases from all the irradiated fuel assernblies in either fuel pool. The lifting devices re-quirement assures that either a single failure vill not result in a drop for the case of redundant lifting devices, or sufficient margin exists such that a failure L.
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vill not occur for the case of a single lifting device. Specification 3 11.8 is
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cpplicable on a one-time-only basis to permit removal of the fuel pool gate from its functional location. The gate shall be removed from its functional location prior to the Cycle 5 refueling outage.
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PROPOSED LiFTINe Loe MoDIFl C ATioN 3HEET \\OF2.
Notes:
1.
All material to be ASTM A240 type 304 2.
Welding to be in accordance with AWS " Structural Welding Code,"
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3.
All welds to be liquid penetrant tested.
4.
Ik" anchor shackle with screw pin shall be used to attach rigging to attachment lugs.
(McMaster-Carr catalog No. 3558T56) 5.
Each attachment lug to be attached to main hook with rigging having working capacity of 22.8k + Sin p or greater.
6.
Design Load P = 3(W + D) where P = design load W = gate weight D = dynamic load k
k P = 3 5k +.32 cs )] = 22.8
References:
Presray Corp. Dwg. PR2416 - Canal Gate 110 ton main hoist A A T o B E-SEE NOTE 5.
o GREATER THA,N 45 L.A E
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